68-Er-166 JAEA EVAL-NOV11 K. Shibata (JAEA) JNST 49, 824 (2012) DIST-DEC21 20180515 ----JENDL-5 MATERIAL 6837 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2011-11 Re-evaluated /1/ by K.Shibata. 2018-05 Activation cross sections added by K.Shibata. 21-11 revised by O.Iwamoto (MF8/MT4) added MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region: below 3 keV Resolved resonance parameters were taken from Ref./2/ or /3/. The bound level at -40.4 eV has Gamma-n = 0.3953 eV and Gamma-gamma = 0.092 eV. This choice gives the desired value for the thermal capture cross section, 16.2 b. Values of Gamma-gamma not given in Ref./2/ or /3/ are set to 0.092 eV. The value for the scattering radius is 0.8295, taken from Ref./4/ with small change within the given error, so as to reproduce the close value of the thermal neutron scattering cross section recommended by Mughabghab /4/. The highest energy resonance included is 2931.8 eV No background cross section is given. In JENDL-4.0, the parameters for 15.56-eV resonance were replaced with those for 15.567-eV resonance measured by Danon et al./3/ Unresolved resonance region: 3 - 200 keV The parameters were obtained by fitting to the calculated total and capture cross sections. The unresolved resonance parameters obtained should be used only for self-shielding calculation. URP's were re-calculated by fitting to the total and capture cross sections calculated by POD /5/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 2.9194E+01 Elastic 1.2447E+01 n,gamma 1.6748E+01 1.1868E+02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /5/. MT= 2 Elastic scattering cross section The elastic scattering cross section was obtained by subtracting the non-elastic cross section from the total cross sections. MT= 3 Non-elastic cross section Calculated with POD code /5/. MT= 4,51-91 (n,n') cross section Calculated with POD code /5/. MT= 16 (n,2n) cross section Calculated with POD code /5/. MT= 17 (n,3n) cross section Calculated with POD code /5/. MT= 22 (n,na) cross section Calculated with POD code /5/. MT= 28 (n,np) cross section Calculated with POD code /5/. MT= 32 (n,nd) cross section Calculated with POD code /5/. MT=102 Capture cross section Calculated with POD code /5/. MT=103 (n,p) cross section Calculated with POD code /5/. MT=104 (n,d) cross section Calculated with POD code /5/. MT=105 (n,t) cross section Calculated with POD code /5/. MT=106 (n,He3) cross section Calculated with POD code /5/. MT=107 (n,a) cross section Calculated with POD code /5/. MT=203 (n,xp) cross section Calculated with POD code /5/. MT=204 (n,xd) cross section Calculated with POD code /5/. MT=205 (n,xt) cross section Calculated with POD code /5/. MT=206 (n,xHe3) cross section Calculated with POD code /5/. MT=207 (n,xa) cross section Calculated with POD code /5/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/5/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/5/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/5/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/5/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/5/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 84 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 85 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 86 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 87 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 88 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 89 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 90 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/5/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/5/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/5/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/5/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/5/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/5/. MF= 8 Information on decay data MT= 16 (n,2n) reaction MT= 17 (n,3n) reaction MT= 22 (n,na) reaction MT= 28 (n,np) reaction MT= 32 (n,nd) reaction MT=102 (n,g) reaction MT=103 (n,p) reaction MT=104 (n,d) reaction MT=105 (n,t) reaction MT=106 (n,He3) reaction MT=107 (n,a) reaction MF= 9 Isomeric branching ratios MT=102 (n,g) reaction Calculated with POD code /5/. Isomeric ratios were modified by considering thermal measurements. MF=10 Nuclide production cross sections MT= 32 Partial (n,nd) reactions Calculated with POD code /5/. MT=103 Partial (n,p) reactions Calculated with POD code /5/. MT=105 Partial (n,t) reactions Calculated with POD code /5/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /5/. MF=14 Gamma-ray angular distributions MT= 3 Non-elastic gamma emission Assumed to be isotropic. MF=15 Gamma-ray spectra MT= 3 Non-elastic gamma emission Calculated with POD code /5/. *************************************************************** * Nuclear Model Calculations with POD Code /5/ * *************************************************************** 1. Theoretical models The POD code is based on the spherical optical model, the distorted-wave Born approximaiton (DWBA), one-component exciton preequilibrium model, and the Hauser-Feshbach-Moldauer statis- tical model. With the preequilibrim model, semi-empirical pickup and knockout process can be taken into account for composite-particle emission. The gamma-ray emission from the compound nucleus can be calculated within the framework of the exciton model. The code is capable of reading in particle transmission coefficients calculated by separate spherical or coupled-channel optical model code. 2. Optical model parameters Neutrons: Coupled-channel optical model parameters /6/ Protons: Koning and Delaroche /7/ Deuterons: Lohr and Haeberli /8/ Tritons: Becchetti and Greenlees /9/ He-3: Becchetti and Greenlees /9/ Alphas: Lemos /10/ potentials modified by Arthur and Young /11/ 3. Level scheme of Er-166 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1* 0.08058 2 + 2* 0.26499 4 + 3* 0.54546 6 + 4 0.78591 2 + 5 0.85939 3 + 6* 0.91121 8 + 7 0.95623 4 + 8 1.07528 5 + 9 1.21596 6 + 10 1.34964 10 + 11 1.37603 7 + 12 1.45816 2 - 13 1.45993 0 + 14* 1.51374 3 - 15 1.52840 2 + 16 1.55574 8 + 17 1.57220 4 - 18 1.59624 4 - 19 1.66240 1 - 20 1.66578 5 - 21 1.67877 4 + 22 1.69228 5 - 23 1.70305 4 + 24 1.72170 3 - 25 1.75140 9 + 26 1.76090 4 + 27 1.78697 6 - 28 1.81320 1 - 29 1.82756 6 - 30 1.83046 1 - 31 1.84660 12 + 32 1.86517 3 - 33 1.89436 4 - 34 1.89727 6 + 35 1.90100 5 - 36 1.90820 6 - 37 1.91776 3 - 38 1.92800 2 - 39 1.93828 3 + 40 1.94800 2 - ------------------------- Levels above 1.95800 MeV are assumed to be continuous. The symbol (*) stands for the excited level involved in the coupled-channel calculation. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /12/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Er-167 19.951 0.929 1.916 0.564 -1.449 6.503 0.878 Er-166 19.758 1.863 2.177 0.540 -0.216 6.951 1.948 Er-165 19.721 0.934 2.568 0.545 -1.312 6.241 0.590 Er-164 19.554 1.874 2.668 0.555 -0.500 7.383 1.798 Ho-166 18.616 0.000 1.715 0.555 -1.814 4.856 0.597 Ho-165 18.868 0.934 2.069 0.556 -1.068 6.014 1.056 Ho-164 19.421 0.000 2.261 0.483 -1.333 3.882 0.343 Dy-164 19.078 1.874 2.014 0.569 -0.344 7.275 1.303 Dy-163 19.156 0.940 2.163 0.569 -1.365 6.445 0.660 Dy-162 18.802 1.886 2.461 0.582 -0.575 7.638 1.767 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /13/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) K.Shibata, J. Nucl. Sci. Technol., 49, 824 (2012). 2) Landolt-Boernstein New Series I/16B (Aug 1998). 3) Y.Danon et al., Nucl. Sci. Eng., 28, 61 (1998). 4) S.F. Mughabghab, "Neutron Cross Sections: Vol. 1, Neutron Resonance Parameters and Thermal Cross Sections, Part B: z=61-100," Academic Press (1984). 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 6) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 7) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 8) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 9) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 10) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 11) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 13) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).